1960年条約における原子力船に関する決定事項（仮訳）

「第１章　一般規定」への追加

第２規則　（定義）
　（j）「原子力船」とは原子力プラントを設置した船舶をいう。

「第８章　原子力船」の新設

原子力船についての「勧告」

１．原子力船の一般的安全性
（a）原子力船における非原子のものの事故、即ち、操舵装置の故障、火災、衝突等を含めた海難は原子力プラントに危険を及ぼす恐れがあるのでこれらの事故に対しても最大の安全性を確保するための対策を講ずることが望ましい。原子力船は本条約の各規則、主管官庁、認められた船級協会の要求を満足しなければならない。水密区劃、防火、ビルヂ排水装置、消火設備、電気設備、操舵装置、後進力、復原性、航海用具等についても原子力プラントに特有な災害を最少限とするための適当な措置を講ずること。過去における海難の結果に照して、同じ程度の大きさの在来船において同様な事故を想定し、その際に放射線又は有害な物質の危険な放出が生じないような考慮を払うべきである。

（b）原子力船についてはその一般構造強度並びに、原子炉室内および周辺の局部強度について特別な考慮を払うべきである。

（c）原子力船は、あらゆる積荷状態において、少くとも如何なる二つの隣接した主要水密区劃が浸水した場合においても浮揚しかつ十分なる復原性を持っているべきである。

（d）防火設備および水密度については、少くとも本条約の最高の基準に同等であること。

２．原子力プラントについての一般的要求
（a）原子力プラントの特性およびその格納が海上又は港内において、乗組員、乗客、公衆、水路、食物又は水産資源に対して不当な放射線の曝射を生ずるような事故又は欠陥に対して最大の防護がなされていることを計算および実験によって確かめられねばならない。

（b）原子炉装置は如何なる運転状態および沈没を含めた事故状態においても無制御な連鎖反応を防止するよう設計されておらねばならない。

（c）１基の原子炉のみをもつ原子力プラントを設置した原子力船は、未だ原子炉の信頼性が証明されていないので、航海し得る速力で船を推進することの出来る非常推進プラントを装備しなければならない。原子力船が領海内を航行する時は、非常推進プラントは常に利用し得る状態にしておかねばならない。

（d）原子カプラントは同様な在来船のものと同等の操縦性を確保しうる如きものであること。

（e）原子力プラントの中の在来部分（非原子力部分）についての予備非常部品についての要求は同様な在来船に対する要求に合致すること。予備及び非常用原子力部会については、使用される原子力プラントの型式に関連して考慮し且つ開発されねばならない。

（f）原子炉装置の安全運転に欠くことの出来ない予備系統は万一の事故に備えて主系統と分離しなければならない。

（g）非常電源は原子炉装置を安全に停止し且原子炉を安全な状態に保持するために必要な部分に電力を供給し得るに足るものを装備せねばならない。

（h）原子炉室には原子炉装置に必要なるものを除き可燃性物質は使用しないこと。

（i）空気又は水と危険な程度に化学的反応を起す如き原子炉材料はその安全性が確認されない限りは使用してはならない。

（j）主機械および原子炉装置は、船の傾斜、加速度、振動について航海状態において満足に運転されるよう設計されなければならない。

（k）原子炉冷却装置は原子炉から崩壊熱を安全に除去し得るものであり且つ、船舶の復原性限度内のヒールおよび傾斜の状態で、予想し得る運転時および事故時に過熱状態になることを防止し得るものであること。崩壊熱除去装置の欠陥が原子炉格納容器からの放射線又は有害物質の危険量の放出を生じないこと。

（l）適切な原子炉制御、防護装置および計測器を装備すること。

（m）原子炉装置を格納施設の外側から制御し得るよう必要な制御装置および計測器を設けること。

３．原子炉装置の防護および格納施設
（a）原子炉装置は、海難時における原子炉事故の可能性を最小限とするよう配置され保護され且安全に固縛されねばならない。

（b）原子炉装置は、事故の時に放射線又は有害物質の危険量が、船内の作業区域、居住区域おび船の周辺に救出されることを防止するための格納施設、系統、装置を設けねばならない。これらは考えられるすべての事故の状態のもとにおいて満足なものであることを確かめるために適当な試験を行わねばならない。

（c）格納施設、系統、装置は衝突又は坐礁時における事故を最小にするような場所に配置されること。構造上、正常なる状態における原子炉の安全性に悪影響を及ぼすことなく、船舶が難破した際に原子炉又はその主要部分を船舶から取り出し得るようにすること。

（d）原子炉装置の内外における火災により格納施設、系統および装置が損われないためおよび原子炉装置を安全に停止し、安全な状態に保持するための設備を備えること。

４．遮蔽および放射線防護
（a）原子力プラントは、船上又は船のすぐ外側にいる人々を正常および事故時において救射線の危険から保護するため信頼される生体遮蔽を備えなければならない。船内居住区域における放射線の最大許容限度は、国際的基準が確立されたときにはこれに従うこと。

（b）適切な放射線防護に関する基準、取扱いは、すべての原子力船のために作られねばならない。原子力プラント関係者のこれらに関する知識は、主管官庁によって定期的に試験されねばならない。

（c）適当な個所に放射線監視機器を設置すること。これらの監視機器は、放射線が予め定められた安全レベルを超えた場合に警報を発すること。

５．放射性廃棄物
（a）原子力船は安全な一時的貯蔵庫を設けて固体、液体および気体の放射性廃棄物の安全な処理に備えること。

（b）これら放射性廃棄物処理施設には監視装置を備えること。これら監視装置は放射線が予め定められた安全レベルを超えた場合に警報を発すること。

（c）公海における廃棄物処理の放射線の最大許容レベルは、国際的基準が確立された時にはこれに従うこと。

６．燃料装荷およびその取扱い
（a）原子炉の燃料装荷はこの目的のために適切な設備をもった場所で行なわれなければならない。

（b）燃料の取出し、燃料の交換およびその取扱いは、人間に対して不当な放射線の曝射をすることなく、又周辺に対して放射性又は有害な物質の危険な放出を生じないようにして行なわれなくてはならない。

７．乗　組　員
　原子力船の船長、士官、船員は主管官庁の定める資格を所有し且つ、その定める責任と義務を遂行するための適切な訓練を受けなければならない。これらの人々は、又放射線防護に関しても教育を受けなければならない。

８．運転方法書
　運転方法書には定常状態および事故時における各種機器装置の取扱いについての詳細、運転の記録、放射線の強さ、廃棄物の処理、原子炉施設の安全性に関する試験および検査についての方法について記載すること。

９．安全審査書
（a）安全審査書には資格ある人が原子力船および原子力プラントの安全性を確認し、又最初および連続運転が安全であるか否かを決定するために十分なる詳細な資料を記載すること。安全審査書に記載すべき事項は少くとも、原子力船の仕様、推進装置および原子炉系の仕様、通常の海上、港内および非常時における運転状況についての検討、原子炉制御、原子炉の保護および格納施設、放射線防護、放射性廃棄物の処理、燃料装荷、予備および非常用備品、試験方法、乗組員およびその資格、危険を最小限とすることを示す事故解析の評価に亘ること。安全審査書には原子炉施設が乗組員、乗客、公衆、水路、食物、水産資源に不当な危険を及ぼさないものであることについても記述されねばならない。

（b）安全審査書の内容は上に例記したものに限定されるものではなく、必要と考えられる追加資料も提供されるべきである。完成された安全審査書は、同一船型の同一型式の原子炉のものの最初のものについて作成されねばならない。運転経験と安全性が実証された同船型、同型式の原子炉の第２船以降のものについては、以前の設計との差異についての解析のみにて承諾されるであろう。

10．原子力船受入れについての要求の公表
　締約国政府は原子力船のその国の港への接近、入港碇泊についての特別な要求を行なう時はこれを公表しなければならない。

11．特別な監督
　原子力船およびその原子力プラントの安全性が十分確認された上は、一般的に、その安全な運航を判断するためには次の措置をとることが適当である。

（a）原子力プラント及び附属機器の運転日誌を最終寄港地を含めて１週間乃至１ヵ月の適当な期間にわたって検証すること。

（b）原子力プラントが妥当に証明されたものであるか否か、および運転方法書の要求する定期的な点検が行なわれているか否かを確かめること。

（c）原子力船の内部および周辺の住民の近づき得る原子力船の近傍における放射線レベルが、運転方法書に述べられた最大許容レベルを超えていないことを船の記録で検証するか又は直接測定するかして確かめること。

（d）原子力船上に貯蔵されている放射性廃棄物の数量及び放射能を船の記録又は直接測定によって確かめること。又廃棄物処理の方法及び予定について確かめること。

（e）原子炉施設の防護および格納施設が完全であるか否かの確認、およびこれら施設が損傷した場合の対策が運転方法書の要求と合致しているか否かを確認すること。

（f）狭い水路を航行する時に特に信頼性を必要とする在来機器および非常用機器が有効に使用し得る状態にあるか否かを確認すること。

CHAPTER I GENERAL PROVISIONS

PART A-APPLICATION, DEFINITIONS, ETC.
Regulation 2 Definitions

　 For the purpose of the present Regulations, unless expressly provided otherwise : -
(j) A nuclear ship is a ship provided with a nuclear power plant.

CHAPTER VIII NUCLEAR SHIPS

Regulation 1 Application
　 This Chapter applies to all nuclear ships except ships of war.

Regulation 2 Application of other Chapters
　 The Regulatios contained in the other Chapters of the present Convention apply to nuclear ships except as modified by this Chapter.

Regulation 3 Exemptions
　 A nuclear ship shall not, in any circumstances, be exempted from compliance with any Regulations of this Convention.

Regulation 4 Approval of Reactor Installation
　 The design, construction, and standards of inspection and assembly of the reactor installation shall be subject to the approval and satisfaction of the administration and shall take account of the limitations which will be imposed on surveys by the presence of radiation.

Regulation 5 Suitability of Reactor Installation for Service on board Ship
　 The reactor installation shall be designed having regard to the special conditions of service on board ship both in normal and exceptional circumstances of navigation.

Regulation 6 Radiation Safety
　 The Administration shall take measures to ensure that there are no unreasonable radiation or other nuclear hazards, at sea or in port, to the crew, passengers, or public, or to the waterways or food or water resources.

Regulation 7 Safety Assessment
(a) A Safety Asseessment shall be prepared to permit evaluation of the nuclear power plant and safety of the ship to ensure that there are no unreasonable radiation or other hazards, at sea or in port, to the crew, passengers or public, or to the waterways or food or water resources. The Administration, when satisfied, shall approve Such Safety Assessment which shall always be kept up-to-date.

(b) The Safety Assesment shall be made available sufficiently in advance to the Contracting Governments of the countries which a nuclear ship intends to visit so that they may evaluate the safety of the ship.

Regulation 8 Operating Manual
　 A fully detailed Operating Manual shall be prepared for the information and guidance of the operating personnel in their duties on all matters relating to the operation of the nuclear power plant and having an important bearing on safety. The Administration, when satisifed, shall approve Such Operating Manual and a copy shall be kept on board the ship. The Operating Manual shall always be kept up-to-date.

Regulation 9 Surveys
　 Survey of nuclear ships shall include the applicable requirements of Regulation 7 of Chapter I, or of Regulations 8, 9 and 10 of Chapter I, except insofar as surveys are limited by the presence of radiation. In addition, the surveys shall include any special requirements of the Safety Assessment.

　 They shall in all cases, not withstanding the provisions of Regulations 8 and 10 of Chapter I, be carried out not less frequently than once a year.

Regulation 10 Certificates
(a) The provisions of sub-paragraph (a) of Regulation 12 of Chapter I and of Regulation 14 of Chapter I shall not apply to nuclear ships.

(b) A Certificate, called a Nuclear Passenger Ship Safety Certificate shall be issued after inspection and survey to a nuclear passenger ship which complies with the requirements of Chapters II, III, IV, and VIII, and any other relevant requirements of the present Regulations.

(c) A Certificate, called a Nuclear Cargo Ship Safety Certificate shall be issued after inspection and survey to a nuclear cargo ship which satisfies the requirements for cargo ships on survey set out in Regulation 10 of Chapter I, and complies with the requirements of Chapters II, III, IV and VIII, and any other relevant requirements of the present
Regulations.

(d) Nuclear Passenger Ship Safety Certificates and Nuclear Cargo Ship Safety Certificates shall state: "That the ship, being a nuclear ship, complied with all requirements of Chapter VIII of the Convention and conformed to the Safety Assessment approved for the ship."

(e) Nuclear Passenger Ship Safety Certificates and Nuclear Cargo Ship Safety Certificates shall be valid for a period of not more than 12 months.

(f) Nuclear Passenger Ship Safety Cerilficates and Nuclear Cargo Ship Safety Certificates shall be issued either by the Administration or by any person or organization duly authorized by it. In every case, that Administration assumes full responsibility for the certificate.

Regulation 11 Special Control
　 In addition to the control established by Regulation 19 of Chapter I, nuclear ships shall be subject to special control before entering the Ports and in the ports of Contracting Governments, directed towards verifying that there is on board a valid Nuclear Ship Safety Certificate and that there are no unreasonable radiation or other hazards at sea or in port, to the crew, passengers or public, or to the waterways or food or water resources.

Regulation 12 Casualties
　 In the event of any accident likely to lead to an environmental hazard the master of a nuclear ship shall immediately inform the Administration. The master shall also immediately inform the competent Govemmental authority of country in whose waters the ship may be, or whose waters the ship approaches in a damaged condition.

RECOMMENDATIONS APPLICABLE TO NUCLEAR SHIPS

Note: Throughout the following Recommendations, "present Convention" means the "International Convention for the Safety of Life at Sea, 1960."

　 Attention is drawn to the Regulations conceming nuclear ships in. Chapter VIII of the present Convention.

1. General Safety of Nuclear Ships
(a) Since a casualty involving the non-nuclear features of a nuclear ship, such as a steering gear failure, fire or collision, and so forth, could endanger the nuclear power plant, it is desirable that these features should provide for the maximum practicable safety. A nuclear ship should comply with the relevant requirements of the present Con vention, the Administration and a recognised Classification Society. Components and systems such as water-tight sub-division, Are protection, bilge pumping arrangements, fire extinguishing arrangements, electrical installations, steering gear, astern power, stability and navigational aids should receive special consideration to ensure that adequate protection is given to the ship to minimise the hazards peculiar to the nuclear power plant. Consideration should be given to the results of past marine casualties involving similar size ships with the intent of preventing the dangerous uncontrolled release of radioactive or toxic materials in the event of similar casualties.

(b) Special attention should be given to general strength of structural strength of nuclear ships and to the local structures in and around the reactor compartment.

(c) A nuclear ship should remain aaoat and have sufficient stability when not less than any two adjacen tmain watertight compartments are flooded, in all anticipated conditions of loading.

(d) Fire protection systems and the watertight integrity should be at least equivalent to the highest standards of the present Convention.

2. General Requirements of Nulcear power Plant
(a) It should be demonstrated by calculation and experiment that the properties of the plant and the nature of the enclosure provide the maximum practicable protection against accidents or failures resulting in unreasonable radiation at sea or in port, to the crew, passengers, or public, or to the waterways, or food or water resources.

(b) The reactor installation should be designed to prevent an uncontrolled chain reaction under all foreseeable operational and accident conditions including sinking of the ship.

(c) A nuclear ship equipped with a single-reactor nuclear power plant, the dependability of which has not been proven, Should be provided with an emergency propulsion plant capable of propelling the ship at a navigable speed. Such emergency propulsion plant should be in a state of readiness whenever the ship is navigating in territorial waters.

(d) The nuclear power plant should be such as to ensure manoeuvrability equivalent to that of a similar conventional ship.

(e) Requirements for standby emergency components for the conventionai portions of the nuclear power plant should be in accordance with those for a similar conventional ship. Standby and emergency nuclear components should be considered and developed in relation to the type of nuclear power plant used.

(f) Where standby systems are essential to the safe operation of the reactor installation, they should be so separated from the main systems as to give maximum protection in the event of an accident.

(g) An emergency source of power should be provided which is capable of fumishing power to the components necessary for safely shutting down the reactor installation and retaining it in a safe condition.

(h) The reactor compartment should contain no inflammable materials other than those necessary for use in the reactor installation.

(i) Reactor materials which are chemically reactive with air or water to a dangerous degree should not be used unless it can be shown that adequate safeguards are incorporated in the particular stem.

(j) The machinery and reactor installation should be designed to operate satisfactorily under seagoing conditions having regard to the ship's attitude, accelerations and vibrations.

(k) Reactor cooling systems should provide for the safe removal of decay heat from the reactor and should prevent excessive temperature conditions under all foreseeable cperational and accident conditions at angles of heel and list within the stability range. Failure of decay heat removal facilities should not result in the release of hazardous amounts of radioactive or toxic materials from the enclosure of the reactor installation.

(l) Adequate reactor controls. protective devices and instrumentaLtion should be provided.
(m) Necessary controls and instrumentation should be arranged to permit control of the reactor installation from outside its enclosure.

3. Protection and Enclosure of Reactor Installation
(a) The reactor installation should be so arranged, protected and securely fastened as to minimize the probability of its damage in the event of a ship accident.

(b) The reactor installation should be provided with enclosures, systems, or arrangements which in the event of damage to its components will prevent the release of hazardous amounts of radioactive or toxic materials into service and accommodation spaces and the ship's environment. These outer enclosures, systems, or. arrangements should be subjected to suitable tests to demonstrate satisfactory performance under all foreseeable conditions of accident.

(c) The enclosures, systems, or arrangements should be kcated in such a manner as to minimize damage in the event of collision or grouding. In construction, arrangements should be made, if practicable, to facilitate the possible salvage of the reactor or of its essential parts from the vessel in the event of shipwreck, without adversely affecting the safety of the reactor instllation under normal conditions.

(d) Facilities should be provided to ensure that fires within and without the reactor installation do not impair the integrity of the enclosures, systens, or arrangements provided, or the arrangements provided for safely shutting down the reactor installation and retaining it in a safe condition.

4. Shielding and Radiation Safety
(a) A nuclear power plant should be provided with reliable biological shielding to protect persons on board ship or within the immediate vicinity of the ship against hazardous effect of radiation under normal and accident conditions. Maximum permissible levels of radiation in accommodation and service spaces should be in accordance with international levels when established.

(b) Maintenance and operation instructions in regard to appropriate radiation protection should be worked out for every nuclear ship. Knowledge of these instructions by the nuclear power plant personnel should be periodically checked by the Administration.

(c) Radiation monitoring instruments should be installied at appropriate locations. These should give waning in the event of any radiation exceeding a predetermined safe level.

5. Radioactive Wastes
(a) Special arrangements should be provided for the safe temporary storage, where necessary, and for the safe disposal of solid, liquid and gaseous radioactive wastes.

(b) Monitoring devices should be provided for these waste disposal systems. These should give waming and, if necessary take action, in the event of any radiation exceeding a predetermined safe level.

(c) The maximum permissible levels oi radiation for waste disposal on the high seas should be in accordance with international levels when established.

6. Fuelling and Maintenance
(a) Reactor fuelling shoud be carried out exclusively at locations suitably equipped for this purpose.

(b) Arrangements should be provided to ensure that de-fuelling, refuellig, servising and maintenance can be carried oui without unacceptable exposure of personnel to radiation and without hazardous release of radioactive or toxic materils to the environment.

7. Manning
　 The master, officers and members of the crew of a nuclear ship should possess qualifications and have undergone proper training appropriate to their responsibilties and duties in accordance with arrangements provided by the Administration. Such personnel should also be instructed as to the precautions to be taken in the matter of radiological protection.

8. Operating Manual
　 The operating Manual should provide detailed operatig procedures for the various equipment and systems under normal and accident conditions, as well as provide for the maintenance of adequate records of operration, radiation levels, waste disposal, and tests and inspections pertnent to the safety of the reactor installation.

9. Safety Assessment
(a) The Safefty Assessment should include sufficiently detailed infomation to permit qualified personnel to assess the safety of the ship and its power plant, including standards and procedures followed, and to determine whether initial and continued perfomance will be safe. Typical items which the safety assessment should include are a discrption of the ship; propulsion and reactor systems a discussion of the operation under normal sea, port and emergency conditions; a discription of reactor control ; protection and enclosure ; radiation protection; radioactive waste disposal; fuelling; standby and emergency components ; test procedures ; manning and training requirement; and an evaluation of credible accidents which indicates that the hazrds are minimised. The Safety Assessment should indicate that the reactor installation does not constitute an undue hazard, to the crew, passengers, or the public, or to the waterways, or food or water resources.

(b) The content of the Safety Assessment should not be considered limited to the information suggested herein; and such additional specific data as necessary should be made available. The complete Safety Assessment should be prepared for the first installation of a reactor type in a ship type. For second and following generation reactor and ship types where performance and safety have been demonstrated, accpetance may be based on an analysis of deviations from the previous design.

10. Publication of Requirements
　The Contracting Governments should publish any special requirements which they make regarding the approach, entry into, or stay in their ports of a nuclear ship.

11. Special Control
　After the safety of the nuclear ship and its nucler power plant has been properly established, the following actions should, in general, be adequate to determine their safe operational and conditions : -

(a) Examination of the daily log of the behaviour of the nuclear power plant and equipment, covering a reasonable period of between one week to one month including the stay in the last port.

(b) Determination that the nuclear power plant is properly certified and that any periodic checks required by the Operating Manual have been complied with.

(c) Determination that radiation levels in areas within the ship and in the vicinity of the ship which are accessible to shore personnel are not in excess of maximum permissible levels specified by the Operating Manual to be determined by examination of the ship's records or by independent measurement.

(d) Determination of the quantity and activity of radionctive waste stored abord the ship by examination of the ship's records or by independent measurement, and of the prccedures and programme for any disposal.

(e) Determination that the reactor installation protection and enclosure is intact, and that any programme involving a breach of its integrity complies with the requirements of the Operating Manual.

(f) Determinaton that convetional and emergency arrangements and equipment, the reliability of which is essential when navigating in narrow waters, are in efhcient operating condition.

Form of Safety Certificate for Nuclear Passenger Ship

NUCLEAR PASSENGER SHIP SAFETY CERTIFICATE

(Seal)

(Signature)

Form of Safety Certificate Nuclear Cargo Ship

NUCLEAR CARGO SHIP SAFETY CERTIFICATE

I. That the above-mentioned ship has been duly surveyed in accordance with the provisions of the Convention referred to above.

II. That the ship, beging a nuclear ship, complied with all requirements of Chapter VIII of the Convention and conformed to the Safety Assessment approved for the ship.

III. That the survey showed that the ship satisfied the requirements set out in Regulation 10 of Chapter I of the Covnention as to hull, machinery and equipment, and complied with the relevant require- ments of Chapter II.

IV. That the life-saving appliances provide for a total number of persons and no more, viz:-
･･････lifeboats on port side capable of accommodating･･････persons
･･････lifeboats on starboard side capable of accommodating
･･････Persons
･･････motor lifeboats (included in the total lifeboats shown above) , including･･･motor lifeboats fitted with radiotele graph installation and searchlight, and･･･motor lifeboat fitted with searchlight only, ･･････liferafts, for which approved launching devices are required, capable of accommodating･･････ persons; and ･･････liferafts, for which approved launching devices are not required, capable of accommodating
･･････persons;
･･････lifebuoys;
･･････lifejackets.

V. That the lifeboats and liferafts were equipped in accordance with the provisions of the Regulations annexed to the Convention.

VI. That the ship was provided with a linethrowing apparatus and portable radio apparatus for survival craft in accordance with the provisions of the Regulations.

VII. That the ship complied with the requirements of the Regulations as regards radiotelegraph installations, viz: -

VIII. That the functioning of the radiotelegraph installations for motor lifeboats and/or the portable radio apparatus for survival craft, if provided, complied with the provisions of the Regulations.

IX. That the inspection showed that the ship complied with the requirements of the said Convention as regards fire-extinguishing appliances and was provided with navigation lights and shapes, pilot ladder, and means of making sound signals and distress signals in accordance with the provisions of the Regulations and the International Collision Regulations.

X. That in all other respects the ship complied with the requirements of the Regulations so far as these requirements apply thereto.

　This certificate is issued under the authority of the Government. It will remain force until Issued at the day of 19 .

　Here follows the seal or signature of the authority entitled to issue the certificate. If signed, the following paragraph is to be added: -

　The undersigned declares that he is duly authorised by the said Government to issue this Certificate.

(Signature)

NOTE
　It will be sufficient to indicate the year in which the keel was laid except for 1952 and the year of coming into force of the Intemational Convention for the Safety of Life at Sea, 1960 in which cases the actual date should be given.

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